CN102176047A - Neutron personal dosimeter with energy compensation - Google Patents
Neutron personal dosimeter with energy compensation Download PDFInfo
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- CN102176047A CN102176047A CN2011100517743A CN201110051774A CN102176047A CN 102176047 A CN102176047 A CN 102176047A CN 2011100517743 A CN2011100517743 A CN 2011100517743A CN 201110051774 A CN201110051774 A CN 201110051774A CN 102176047 A CN102176047 A CN 102176047A
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- neutron
- quantimeter
- personal dosimeter
- dosimeter
- energy
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- 239000000463 material Substances 0.000 claims abstract description 31
- 229920000573 polyethylene Polymers 0.000 claims abstract description 18
- 239000007787 solid Substances 0.000 claims abstract description 13
- 238000006243 chemical reaction Methods 0.000 abstract description 16
- 230000000694 effects Effects 0.000 abstract description 10
- 229910052796 boron Inorganic materials 0.000 abstract description 7
- 238000005516 engineering process Methods 0.000 abstract description 7
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 abstract description 6
- 239000004698 Polyethylene Substances 0.000 abstract description 3
- 238000001514 detection method Methods 0.000 abstract description 3
- -1 polyethylene Polymers 0.000 abstract description 3
- 230000005855 radiation Effects 0.000 abstract description 3
- 229920003023 plastic Polymers 0.000 description 9
- 239000004033 plastic Substances 0.000 description 9
- 238000013461 design Methods 0.000 description 5
- 238000005259 measurement Methods 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 4
- 239000002245 particle Substances 0.000 description 4
- 238000000034 method Methods 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000011160 research Methods 0.000 description 3
- 238000012360 testing method Methods 0.000 description 3
- HGAZMNJKRQFZKS-UHFFFAOYSA-N chloroethene;ethenyl acetate Chemical compound ClC=C.CC(=O)OC=C HGAZMNJKRQFZKS-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000004980 dosimetry Methods 0.000 description 1
- 238000005530 etching Methods 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000005025 nuclear technology Methods 0.000 description 1
- 230000008092 positive effect Effects 0.000 description 1
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Abstract
The invention belongs to the radiation dose measuring technology, and particularly relates to a neutron personal dosimeter with energy compensation. The structure of the dosimeter comprises a dosimeter shell, a gamma detection element and a solid track detector, wherein the dosimeter shell is made of a boron-containing polyethylene material, an air containing cavity is arranged in the dosimeter shell made of the boron-containing polyethylene material, and the solid track detector is arranged in the air containing cavity. The invention adopts two types of conversion bodies, namely an air layer and a boron-containing material, and realizes the effect of energy compensation by the application of the conversion bodies.
Description
Technical field
The invention belongs to the radiation dose measurement technology, be specifically related to a kind of neutron personal dosimeter with energy compensating.
Background technology
Neutron personal dose research is a very important scientific research field, and scientific research and using value are all very high.The occasion that the neutron personal dose monitoring is used comprises nuclear power reactor, experimental reactor, nuclear fuel cycle, nuclear military affairs, Application of Nuclear Technology or the like, and along with China's economy and science and technology development, the continuous foundation of neutron application of radiation field, the neutron personal dosimeter must be more widely used.
Utilizing solid state track detector to carry out the neutron personal dosimetry, is a kind of technology that generally adopts, and solid state track detector can be measured multiple particle, and measuring recoil proton is one of them.At present international, the domestic this technology that adopts mostly that goes up promptly realizes measurement to neutron dose by surveying recoil proton.Present personal dosimeter generally carries out γ monitoring and neutron monitoring simultaneously, but normally used method is directly to place CR-39 solid state track detector isotonic detecting element in quantimeter.The material of quantimeter generally uses common plastic materials such as tygon, has covered the plastic layer of several millimeters thick like this at the neutron detection component ambient, utilizes the hydrogen in the plastics that recoil proton is provided.The typical structure of using of personal dosimeter is provided with γ detecting element 2 and neutron detection element 3 as shown in Figure 1 in quantimeter shell 1 (polyethylene layer) at present.
Such structure can realize the measurement to neutron dose, but also exist very big problem, it is bad mainly to show as energy response, promptly the neutron of energy below 100keV there is not response substantially, also very low to the neutron response of energy below 300keV, concrete neutron energy responds as shown in Figure 2, and this certainly will bring very big influence to the accuracy of dose monitoring.And should be concerned about the all-round response of distinguishing as a kind of good quantimeter, for the neutron personal dosimeter, from the thermal neutron to 15MeV, all should have smooth energy response comparatively continuously.
Summary of the invention
The objective of the invention is to above-mentioned defective, a kind of neutron personal dosimeter with energy compensating is provided, thereby improves the characteristic of energy response of neutron personal dosimeter at existing neutron personal dosimeter.
Technical scheme of the present invention is as follows: a kind of neutron personal dosimeter with energy compensating, comprise the quantimeter shell, and γ detecting element and solid state track detector, wherein, described quantimeter shell adopts the boracic polythene material.
Further, aforesaid neutron personal dosimeter with energy compensating, wherein, in the described boracic polythene material
10The content of B is not less than 2%.
Further, aforesaid neutron personal dosimeter with energy compensating wherein, is provided with the air cavity volume in the quantimeter shell of boracic polythene material, and described solid state track detector is arranged in the air cavity volume.
Further, aforesaid neutron personal dosimeter with energy compensating, wherein, described air cavity volume hollow thickness of gas is not less than 3mm.
Further, aforesaid neutron personal dosimeter with energy compensating wherein, comprises two groups of γ detecting elements, is separately positioned on the quantimeter enclosure both sides of boracic polythene material.
Beneficial effect of the present invention is as follows: the present invention has adopted the conversion body of two kinds of forms, and the one, air layer, the 2nd, contain boron material.By the application of these conversion bodies, realized the effect of energy compensating.Sheathing material contains on the H basis at plastic material have been increased
10The composition of B so not only has recoil proton, also provides
10The charged particle of B nuclear reaction; The air cavity volume provides the air conversion layer of adequate thickness, and the proton in the nuclear reaction of N in the air can be provided, and has further improved the effect of energy compensating.The requirement that quantimeter is generally monitored neutron and gamma-rays dosage has simultaneously been satisfied in the measuring position of two groups of gamma-rays elements design.
Description of drawings
Fig. 1 is the structure principle chart of existing neutron personal dosimeter;
Fig. 2 is the typical neutron energy response of an existing neutron personal dosimeter synoptic diagram;
Fig. 3 is the structure principle chart of neutron personal dosimeter of the present invention;
Fig. 4 is the neutron energy response synoptic diagram of neutron personal dosimeter of the present invention.
Embodiment
Below in conjunction with drawings and Examples the present invention is described in detail.
Quantimeter measurement recoil proton is actually and has utilized following nuclear reaction:
n+H→n+p
H is wherein provided by plastics such as tygon, if so by the change of quantimeter material, can utilize other nuclear reaction, produces extra charged particle, just can improve the response of quantimeter to low-energy neutron.
This material should be bigger for the neutron reaction cross section of low energy end, and so in general material mainly contains
3He,
6Li,
10B, Au etc.
3He is an inert gas, is difficult to use.The cost of Au is also high and tissue equivalent's property is poor, is not suitable for doing the quantimeter material.Therefore,
6Li and
10B can be used as main consideration object, but considers the problems such as processibility of quantimeter, and it is the most feasible using plastic material, and above two kinds of materials can be easier to form plastics
10B realizes more easily, so the present invention adopts the main material of boracic polythene material as quantimeter, in the hope of reaching the effect of low energy end energy compensating.Utilize
10B measures neutron and mainly utilizes following nuclear reaction:
n+
10B→
7Li+α+2.792MeV(6.1％)
7Li*+α+2.31MeV(93.9％)
7Li*→
7Li+γ+0.478MeV
Contain 20% in the natural boron approximately
10B, major part is
11B, the boron that adds in plastics also are a spot of, and be therefore general
10The content of B is lower, and the actual utilization of the present invention is so
10B, obviously
10The content of B is the effect that can have influence on energy compensating.By a certain amount of test, definite can play apparent in view energy compensating effect
10B content should be not less than 2%.
Based on above-mentioned result of study, the neutron personal dosimeter with energy compensating provided by the present invention comprises quantimeter shell 4, and γ detecting element 5 and CR-39 solid state track detector 6, wherein, described quantimeter shell adopts the boracic polythene material, in the boracic polythene material
10The mass content of B is not less than 2%, and its structure as shown in Figure 3.In polythene material
10The content of B is satisfying under the prerequisite of concrete manufacture craft, and content is high more, and the energy compensating effect is good more.In conjunction with the synthetic characteristics of polythene material, in general in the boracic polythene material
10The mass content of B is between 2%～10%.
Just compensation can also as long as there is nuclear reaction that charged particle is provided, just can play a role by other method, and there are reaction in neutron and airborne N, and reaction equation is as follows:
n+
14N→
14C+p
This reaction also can provide solid state track detector detectable proton.If utilizing the appropriate design of quantimeter structure is the compensation effect that can reach certain, the present invention designs certain air cavity volume 7 in quantimeter, and as shown in Figure 1, CR-39 solid state track detector 6 is arranged in the air cavity volume 7.Thereby utilize the air conversion body, the certain energy compensation effect is provided.And normally used quantimeter solid trace detecting element generally is close to plastic casing.In design,, determined air cavity volume hollow thickness of gas, should be not less than 3mm, the comparatively compensation effect of positive effect just can be provided by certain test.The thickness of air layer is limited by the size of quantimeter, for the stock size of present neutron personal dosimeter, in general the thickness of air layer can be determined between 3～10mm.
Above technical scheme comprises that the selection of quantimeter material and quantimeter structure Design constitute core of the present invention, cooperate suitable track etching method on this basis, greatly improved the characteristic of energy response of neutron personal dosimeter, show by test, quantimeter has goodish characteristic of energy response from the thermal neutron to 15MeV, the limit that its energy response changes is better than 21%, be a kind of neutron personal dosimeter with more satisfactory characteristic of energy response, the energy response of this quantimeter as shown in Figure 4.
In addition, quantimeter has also designed the measuring position of two groups of gamma-rays elements, respectively in the quantimeter enclosure both sides of boracic polythene material, generally monitors the requirement of neutron and gamma-rays dosage simultaneously to satisfy quantimeter.
By using the neutron irradiation quantimeter of the present invention of different-energy, its characteristic of energy response is as shown in table 1:
Table 1 energy response experimental data
Obviously, those skilled in the art can carry out various changes and modification to the present invention and not break away from the spirit and scope of the present invention.Like this, if of the present invention these are revised and modification belongs within the scope of claim of the present invention and equivalent technology thereof, then the present invention also is intended to comprise these changes and modification interior.
Claims (5)
1. the neutron personal dosimeter with energy compensating comprises the quantimeter shell, and γ detecting element and solid state track detector, it is characterized in that: described quantimeter shell adopts the boracic polythene material.
2. the neutron personal dosimeter with energy compensating as claimed in claim 1 is characterized in that: in the described boracic polythene material
10The content of B is not less than 2%.
3. the neutron personal dosimeter with energy compensating as claimed in claim 1 or 2 is characterized in that: be provided with the air cavity volume in the quantimeter shell of boracic polythene material, described solid state track detector is arranged in the air cavity volume.
4. the neutron personal dosimeter with energy compensating as claimed in claim 3 is characterized in that: described air cavity volume hollow thickness of gas is not less than 3mm.
5. the neutron personal dosimeter with energy compensating as claimed in claim 1 or 2 is characterized in that: comprise two groups of γ detecting elements, be separately positioned on the quantimeter enclosure both sides of boracic polythene material.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201110051774 CN102176047B (en) | 2011-03-04 | 2011-03-04 | Neutron personal dosimeter with energy compensation |
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|---|---|---|---|
| CN 201110051774 CN102176047B (en) | 2011-03-04 | 2011-03-04 | Neutron personal dosimeter with energy compensation |
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| CN102176047A true CN102176047A (en) | 2011-09-07 |
| CN102176047B CN102176047B (en) | 2013-04-17 |
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102569487A (en) * | 2012-01-17 | 2012-07-11 | 北京大学 | Silicon PIN neutron dose detector and manufacturing method thereof |
| CN102928866A (en) * | 2011-08-09 | 2013-02-13 | 中国辐射防护研究院 | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector |
| CN104174121A (en) * | 2013-05-22 | 2014-12-03 | 住友重机械工业株式会社 | Neutron capture therapy apparatus and neutron beam measuring method |
| WO2017206485A1 (en) * | 2016-06-01 | 2017-12-07 | 南京中硼联康医疗科技有限公司 | Radiation dose measuring method |
| CN109839657A (en) * | 2017-11-28 | 2019-06-04 | 中国辐射防护研究院 | A kind of method of dosimeter energy response Compensation Analysis |
| CN114152635A (en) * | 2021-10-15 | 2022-03-08 | 中国人民解放军军事科学院军事医学研究院 | Equivalent simulation device for neutron energy spectrum in human blood vessel after neutron external irradiation |
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| WO1991017462A1 (en) * | 1990-04-27 | 1991-11-14 | Hitachi, Ltd. | Neutron exposure dosimeter for individual use, neutron dose rate meter, neutron detector and method of producing them |
| CN1746217A (en) * | 2005-10-21 | 2006-03-15 | 北京市射线应用研究中心 | Composite shielding materials with lead boron polythene material and preparation thereof |
| CN201017035Y (en) * | 2006-04-03 | 2008-02-06 | 李建平 | Novel high-sensitivity surroundings neutron detector |
| CN202066972U (en) * | 2011-03-04 | 2011-12-07 | 中国原子能科学研究院 | Personal neutron dosimeter with energy compensation |
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2011
- 2011-03-04 CN CN 201110051774 patent/CN102176047B/en active Active
Patent Citations (5)
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| GB919192A (en) * | 1958-09-05 | 1963-02-20 | Saint Gobain | A neutron flux dosimeter |
| WO1991017462A1 (en) * | 1990-04-27 | 1991-11-14 | Hitachi, Ltd. | Neutron exposure dosimeter for individual use, neutron dose rate meter, neutron detector and method of producing them |
| CN1746217A (en) * | 2005-10-21 | 2006-03-15 | 北京市射线应用研究中心 | Composite shielding materials with lead boron polythene material and preparation thereof |
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Non-Patent Citations (1)
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102928866A (en) * | 2011-08-09 | 2013-02-13 | 中国辐射防护研究院 | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector |
| CN102928866B (en) * | 2011-08-09 | 2015-05-20 | 中国辐射防护研究院 | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector |
| CN102569487A (en) * | 2012-01-17 | 2012-07-11 | 北京大学 | Silicon PIN neutron dose detector and manufacturing method thereof |
| CN102569487B (en) * | 2012-01-17 | 2014-05-28 | 北京大学 | Silicon PIN neutron dose detector and manufacturing method thereof |
| CN104174121A (en) * | 2013-05-22 | 2014-12-03 | 住友重机械工业株式会社 | Neutron capture therapy apparatus and neutron beam measuring method |
| CN104174121B (en) * | 2013-05-22 | 2017-05-24 | 住友重机械工业株式会社 | Neutron capture therapy apparatus and neutron beam measuring method |
| WO2017206485A1 (en) * | 2016-06-01 | 2017-12-07 | 南京中硼联康医疗科技有限公司 | Radiation dose measuring method |
| US10379227B2 (en) | 2016-06-01 | 2019-08-13 | Neuboron Medtech Ltd. | Radiation dose measuring method |
| CN109839657A (en) * | 2017-11-28 | 2019-06-04 | 中国辐射防护研究院 | A kind of method of dosimeter energy response Compensation Analysis |
| CN109839657B (en) * | 2017-11-28 | 2022-05-20 | 中国辐射防护研究院 | Energy response compensation analysis method for radiation dosimeter |
| CN114152635A (en) * | 2021-10-15 | 2022-03-08 | 中国人民解放军军事科学院军事医学研究院 | Equivalent simulation device for neutron energy spectrum in human blood vessel after neutron external irradiation |
| CN114152635B (en) * | 2021-10-15 | 2024-05-31 | 中国人民解放军军事科学院军事医学研究院 | Equivalent simulation device for neutron energy spectrum in human blood vessel after neutron external irradiation |
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